Estimates of failure rates for nuclear power plant piping systems are important inputs to Probabilistic Risk Assessments (PRA) and risk informed applications of PRA. Such estimates are needed for initiating event frequencies for Loss of Coolant Accidents and internal flooding events and for risk informed evaluations of piping system in-service inspection programs. A critical issue in the estimation of these parameters is the treatment of uncertainties, which can exceed an order of magnitude deviation from failure rate point estimates. Sources of uncertainty include failure data reporting issues, scarcity of data, poorly characterized component populations, and uncertainties about the physical characteristics of the failure mechanisms and root causes. A methodology for quantifying these uncertainties using a Bayes' uncertainty analysis method was developed for the EPRI risk informed in-service inspection program and significantly enhanced in subsequent applications. In parallel with these efforts, progress has been made in the development of pipe failure databases that contain the quantity and quality of information needed to support piping system reliability evaluations. Examples are used in this paper to identify technical issues with previous published estimates of pipe failure rates and the numerical impacts of these issues on the pipe failure rates and rupture frequencies are quantified.
[1]
J. S. You,et al.
The experiences of non-code repairs for nuclear safety-related piping in Taiwan
,
2002
.
[2]
S. Beliczey,et al.
The probability of leakage in piping systems of pressurized water reactors on the basis of fracture mechanics and operating experience
,
1987
.
[3]
K. N. Fleming,et al.
Markov models for evaluating risk-informed in-service inspection strategies for nuclear power plant piping systems
,
2004,
Reliab. Eng. Syst. Saf..
[4]
Bengt O. Y. Lydell,et al.
Pipe failure probability - the Thomas paper revisited
,
2000,
Reliab. Eng. Syst. Saf..
[5]
Kaisa Simola,et al.
Comparative Study of Approaches to Estimate Pipe Break Frequencies
,
2002
.
[6]
W. J. Galyean,et al.
Rates of Initiating Events at U.S. Nuclear Power Plants
,
1998
.
[7]
M. B. Calley,et al.
Component external leakage and rupture frequency estimates
,
1992
.